ML022390105

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Proposed Changes to the Safety System Unavailability Performance Indicators
ML022390105
Person / Time
Issue date: 08/28/2002
From: Beckner W
NRC/NRR/DRIP/RORP
To:
Shapaker, J., NRR/RORP, 301-415-1151
Shared Package
ml022390102 List:
References
OMB 3150-0195, TAC M3216 RIS-02-014
Download: ML022390105 (8)


See also: RIS 2002-14

Text

OMB Clearance No. 3150-0195

UNITED STATES

NUCLEAR REGULATORY COMMISSION

OFFICE OF NUCLEAR REACTOR REGULATION

WASHINGTON, DC 20555-0001

August 28, 2002

NRC REGULATORY ISSUE SUMMARY 2002-14

PROPOSED CHANGES TO THE SAFETY SYSTEM UNAVAILABILITY

PERFORMANCE INDICATORS

ADDRESSEES

All holders of operating licenses for nuclear power reactors, except those who have

permanently ceased operations and have certified that fuel has been permanently removed

from the reactor vessel.

INTENT

The U.S. Nuclear Regulatory Commission (NRC) is issuing this regulatory issue summary (RIS)

to inform addressees that beginning on September 1, 2002, the agency will start a 6-month pilot

program to evaluate changes to the safety system unavailability (SSU) performance indicators

(PIs). The pilot program will be assessed midway through the test period to determine if more

than six months are needed to obtain meaningful results. This RIS and its attachments provide

guidance to participating addressees for submitting PI data to the NRC. Addressee

participation in this pilot program is voluntary. Therefore, this RIS requires no action or written

response on the part of an addressee.

BACKGROUND

The Reactor Oversight Process (ROP) is directly linked to the NRCs mission. That framework

includes cornerstones of safety. Within each cornerstone, a broad sample of information on

which to assess licensee performance in risk-significant areas is gathered from PI data

submitted by the licensees and from the NRCs risk-informed baseline inspections. The PIs are

not intended to provide complete coverage of every aspect of plant design and operation, but

they are intended to be indicative of performance within related cornerstones. The data

submitted by each licensee is used to calculate the PI values, which are then compared to risk-

informed, objective thresholds.

NRC has established a formal process to (1) address questions and feedback from internal and

external stakeholders, (2) make changes to existing PIs and thresholds based on lessons

learned, and (3) develop new PIs and associated thresholds. NRC used this formal process

(documented in NRC Inspection Manual Chapter 0608, Performance Indicator Program) to

evaluate the changes described in this RIS.

Package: ML022390102

RIS 2002-14

Page 2 of 5

SUMMARY OF ISSUE

Results from the ROP Pilot Program (SECY-00-0049, dated February 24, 2000) gave the first

indications that there were problems with the SSU PIs. Other feedback that confirmed this

conclusion were stakeholder feedback from public workshops, NRC/Industry Working Group

meetings, and the ROP feedback process. In response to these problems, NRC formed an ad

hoc committee, the Safety System Unavailability Planning Committee. The Committee has

identified the following major issues: (1) the use of risk-significant system functions versus

design-basis functions, (2) the use of T/2 to estimate fault exposure time in the current SSU PI,

(3) the evaluation of design and performance deficiencies that are not detected through regular

surveillance tests, but rather through the significance determination process (SDP), and (4) the

manner in which support systems (e.g., the component cooling water or service water system)

unavailability should affect the availability of the monitored safety system.

Following the formal PI process, steps have been taken to modify the existing SSU PI.

Numerous public meetings have been held since February 2000 to discuss and develop

alternate SSU PIs and the NRC has agreed to pilot test a set of performance indicators under

the mitigating systems cornerstone. These PIs will be referred to as the mitigating system

performance index (MSPI). The MSPI monitors the performance of the risk-significant functions

of selected systems as described in the guidance documents attached to this RIS. This index

consists of system unavailability and system unreliability elements for the monitored system.

Attachments 1 and 2 provide descriptions of the MSPI.

The following plants have volunteered to participate in the pilot test: Salem 1 and 2,

Hope Creek, Limerick 1 and 2, Millstone 2 and 3, Prairie Island 1 and 2, Braidwood 1 and 2,

Surry 1 and 2, Palo Verde 1, 2, and 3, San Onofre 2 and 3, and South Texas 1 and 2.

The purpose of the pilot program is to collect data to determine whether the MSPI is an

improvement over the existing SSU PIs at indicating performance in the mitigating systems

cornerstone, and does not introduce new unintended consequences.

The NRC will follow its standard practices in conducting the pilot test to determine the efficacy

of the proposed MSPI. This includes considering:

1.

differences between data collected for the current SSU PIs and the MSPI;

2.

the comparability of the data reported for the SSU PI and the MSPI;

3.

the ability of licensees to report the requested data accurately and with minimal need

for clarification;

4.

the ability of the MSPI to reduce the potential for unintended consequences

RIS 2002-14

Page 3 of 5

5.

whether the MSPI will satisfy ROP objectives:

Maintain safety: Can MSPI indicate significant departures from expected

performance that warrant additional attention?

Increase public confidence: Is the MSPI at least as understandable as the current

SSU PI?

Improve the efficiency and effectiveness of NRC processes: Are fewer NRC

resources being spent on single-demand failure SDPs and fault exposure data

issues?

Reduce unnecessary regulatory burden: Does the MSPI reduce licensee reporting

burden and resource expenditure. For example, does the MSPI avoid duplication

of records for the maintenance rule, probabilistic risk assessment, and the ROP

and reduce resources allocated to single demand failure SDP evaluations?

Attachment 3 of this RIS provides additional success criteria which address the technical

adequacy of the MSPI.

NRC will continue to use existing PIs to assess plants participating in the pilot program.

Therefore, no thresholds will be applied to the data reported in the MSPI pilot.

Midway through the 6-month pilot program, the NRC will decide whether to extend the program

to ensure that the test results are meaningful and adequate to gather insights. The reporting

guidance in the attachments to this RIS may be modified during the pilot to reflect insights

gained from table top exercises and the data received.

Based on the results of this pilot program and stakeholder feedback, the NRC will decide

whether to replace current PIs with the MSPI.

VOLUNTARY ACTION

Addressees that choose to participate in the pilot program should conform to the guidance in

this RIS for the voluntary submission of PI data. Send the September 2002 PI data as an

attachment to an e-mail message addressed to pidata@nrc.gov on or before October 21, 2002,

and by the 21st of each month thereafter for the preceding month. Include MSPI Pilot-Test

Data in the subject line of the e-mail. The data reporting phase of the pilot test ends on

March 21, 2003, with the submission of data for the preceding month.

All questions and comments generated by pilot plants and the nuclear industry should be sent

to tch@nei.org. Questions and comments from the NRC and the public should be sent to

reactoroversight@nrc.gov. Questions and comments submitted to this e-mail address will be

discussed and evaluated during the next MSPI Working Group monthly meeting. Responses

will be provided within 2 weeks of the monthly MSPI Working Group meeting.

RIS 2002-14

Page 4 of 5

An external NRC Web site, http://www.nrc.gov/NRR/OVERSIGHT/ASSESS/mspi.html, has

been set up for stakeholders to obtain updated guidance on conducting the pilot program. The

updated guidance will be provided in the form of revisions to the attachments to this RIS,

namely, Attachment 1, Section 2.2, Mitigating Systems Cornerstone, of NEI 99-02,

Regulatory Assessment Performance Indicator Guideline (Draft); and Attachment 2,

NEI 99-02, Appendix F, Methodologies For Computing the Unavailability Index, the

Unreliability Index and Determining Performance Index Validity (Draft).

BACKFIT DISCUSSION

This RIS requires no action or written response. Any action on the part of addressees to collect

and transmit PI data in accordance with the guidance contained in this RIS is strictly voluntary

and, therefore, is not a backfit under 10 CFR 50.109. Therefore, the staff did not perform a

backfit analysis.

FEDERAL REGISTER NOTIFICATION

A notice of opportunity for public comment on this RIS was not published in the Federal

Register because the NRC has worked closely with NEI, industry representatives, members of

the public, and other stakeholders since early 1998 on the development of NRCs Reactor

Oversight Process, including the collection of PI data. The NRC has solicited public comment

on its intent to collect PI data in five Federal Register notices (dated January 22, April 12,

May 26, July 19, and August 11, 1999), four regulatory issue summaries (RIS 99-06 and

RIS 2000-08, Voluntary Submission of Performance Indicator Data; RIS 2000-21, Changes to

the Unplanned Scram and Unplanned Scram with Loss of Normal Heat Removal Performance

Indicators; and RIS 2001-25, NEI 99-02, Revision 2, Voluntary Submission of Performance

Indicator Data), and at numerous public meetings. The NRC will also issue a Federal Register

notice soliciting public comment on the proposed PIs described in this RIS.

PAPERWORK REDUCTION ACT STATEMENT

This regulatory issue summary contains voluntary information collections that are subject to the

Paperwork Reduction Act of 1995 (44 U.S.C. 3501 et seq.). These information collections were

approved by the Office of Management and Budget, clearance number 3150-0195, which

expires October 31, 2002.

The burden to the public for this voluntary information collection is estimated to average 240

hours per response for the initial response and 40 hours4.62963e-4 days <br />0.0111 hours <br />6.613757e-5 weeks <br />1.522e-5 months <br /> per response thereafter. This effort

includes the time for reviewing instructions, searching existing data sources, gathering and

maintaining the data needed, and completing and reviewing the information collection. Send

comments regarding this burden estimate or any other aspect of this information collection,

including suggestions for reducing the burden, to the Records Management Branch (T-6 E6),

U.S. Nuclear Regulatory Commission, Washington, DC 20555-0001, or by Internet electronic

mail to INFOCOLLECTS@nrc.gov; and to the Desk Officer, Office of Information and

Regulatory Affairs, NEOB-10202, (3150-0195), Office of Management and Budget,

Washington, DC 20503.

RIS 2002-14

Page 5 of 5

Public Protection Notification

The NRC may not conduct or sponsor, and a person is not required to respond to, an

information collection unless the requesting document displays a currently valid OMB control

number.

If you have any questions about this matter, contact the person listed below.

/RA/

William D. Beckner, Program Director

Operating Reactor Improvements Program

Division of Regulatory Improvement Programs

Office of Nuclear Reactor Regulation

Technical Contact:

Serita Sanders, NRR

301-415-2956

E-mail: SXS5@nrc.gov

Attachments:

1. Section 2.2, Mitigating Systems Cornerstone, of NEI 99-02,

Regulatory Assessment Performance Indicator Guideline (draft)

2. NEI 99-02, Regulatory Assessment Performance Indicator Guideline,

Appendix F, Methodologies For Computing the Unavailability Index,

the Unreliability Index, and Determining Performance Index Validity (draft)

3. Mitigating System Performance Index Pilot Program Success Criteria (draft)

4. List of Recently Issued NRC Regulatory Issue Summaries

ML022390105

  • See previous concurrence

OFFICE OE:RORP:DRIP

Tech Editor

IIPB:DIPM

SC:IIPB:DIPM

NAME

JWShapaker*

PKleene*

SSanders*

MSatorious*

DATE

08/26/2002

08/22/2002

08/19/2002

08/21/2002

OFFICE BC:IIPM:DIPM

OGC

SC:RORP:DRIP

PD:RORP:DRIP

NAME

CCarpenter*

HMcGurren*

TReis*

WDBeckner

DATE

08/21/2002

08/21/2002

08/27/2002

08/28/2002

Attachment 3

RIS 2002-14

Page 1 of 1

Mitigating System Performance Index Pilot Program

Success Criteria (Draft)

The Mitigating System Performance Index (MSPI) pilot program objectives and success criteria

listed below will be considered to have been met if there is general agreement among the NRC

staff, industry stakeholders, and public stakeholders that they have been met.

1.

The occurrence of a single failure of an MSPI monitored component by itself,

absent any other failures or unavailabilities, should rarely exceed the green/white

MSPI threshold as measured from the baseline value. The term rare is defined

as minimizing the inconsistencies across plants, within plants, and within systems

such that there is no undue burden on resources, and the objective of having

consistent publicly displayed results can be achieved.

2.

False positive and false negative rates can be established for the chosen statistical

method, and instances where the MSPI cannot meet the criteria are rare.

3.

Instances where the results from the MSPI calculational methodology are not

consistent with the SPAR-3 models are rare, and the differences are explainable.

4.

The MSPI pilot plant participants can identify and compile the risk significant

functions for the monitored systems in a readily inspectable format, and can

compile a set of predetermined success criteria for those risk significant functions.

5.

The active components in the monitored systems are appropriate for inclusion in

the MSPI and are a manageable number of components under the MSPI.

6.

By the end of the pilot program, inspection procedures and MSPI pilot guidelines

are sufficiently detailed to minimize MSPI Questions and NRC feedback forms.

7.

MSPI Questions and NRC feedback do not reveal any unresolvable issues.

8.

Data collection inconsistencies between the maintenance rule and the MSPI can

be reconciled in order to eliminate or significantly reduce separate reporting.

9.

Differences between the linear approximation models generated by licensee

probabilistic risk assessments and those generated by the NRC SPAR-3 models

can be reconciled.

______________________________________________________________________________________

OL = Operating License

CP = Construction Permit

Attachment 4

RIS 2002-14

Page 1 of 1

LIST OF RECENTLY ISSUED

NRC REGULATORY ISSUE SUMMARIES

_____________________________________________________________________________________

Regulatory Issue

Date of

Summary No.

Subject

Issuance

Issued to

_____________________________________________________________________________________

2002-13

Confirmation of Employment

Eligibility

08/27/2002

All holders of operating licenses

for nuclear power reactors.

2002-12

NRC Threat Advisory and

Protective Measures System

Various

Various

2002-11

Requalification Program Test

Results for Okonite Okolon Single-

Conductor Bonded-Jacket Cable

(Followup to Regulatory Issue

Summary 2000-25)

08/09/2002

All holders operating licenses for

nuclear power reactors, except

those who have permanently

ceased operations and have

certified that fuel has been

permanently removed from the

reactor vessel.

2002-10

Revision of the Skin Dose Limit in

10 CFR Part 20

07/09/2002

All U.S. Nuclear Regulatory

Commission material licensees.

2002-09

Preparation and Scheduling of

Operator Licensing Examinations

06/06/2002

All holders of operating licenses

for nuclear power reactors, except

those who have permanently

ceased operations and have

certified that fuel has been

permanently removed from the

reactor vessel.

2002-08

Availability of the Topical Report

Program Description and Status of

Staff Reviews on the NRC Web

Site

05/22/2002

All holders of construction permits

or operating licenses for nuclear

power reactors (including those

that have permanently ceased

operations and have certified that

fuel has been permanently

removed from the reactor vessel),

formal nuclear industry groups,

and nuclear steam supply system

vendors.

Note:

NRC generic communications may be received in electronic format shortly after they are

issued by subscribing to the NRC listserver as follows:

To subscribe send an e-mail to <listproc@nrc.gov >, no subject, and the following

command in the message portion:

subscribe gc-nrr firstname lastname